• 한국방재학회 논문집
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• 제9권4호
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• pp.21-28
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• 2009

국내 조선소는 빈번하게 태풍에 의해 영향을 받는 해안에 위치하며, 풍하중에 취약한 많은 경량 구조의 시설물들로 이루어져 있다. 본 연구에서는 주변 지형과 조선소내부 건물의 영향까지 고려하여 시설물의 강풍에 대한 위험 분석을 수행하였다. 몬테카를로 시뮬레이션에 의해 대상 지역의 극한 풍속을 추정하여 전산유체역학 해석을 위한 입사풍속으로 설정하였으며, 난류 유동을 고려한 전산 유체 해석을 이용하여 시설물 표면에 발생하는 풍압과 조선소 사업장 내의 풍속 분포를 추정하였다. 결과로서 일부 시설물에는 설계 하중보다 높은 풍하중이 작용하여 보강이 요구되는 것으로 판단되며, 향후 설계 풍하중을 고려하는 경우 주변의 국부적 지형 변화와 건물 배치를 고려해야 할 것으로 나타났다.

• 비파괴검사학회지
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• 제31권5호
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• pp.543-551
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• 2011

Steam generator tubes for nuclear power plants contain the local shape transitions on their inner or outer surface such as dent, bulge, over-expansion, eccentricity, deflection, and so on by the application of physical force during the tube manufacturing and steam generator assembling and by the sludge (that is, corrosion products) produced during the plant operation. The structural integrity of tubes will be degraded by generating the corrosive crack at that location. The profilometry using the traditional bobbin probes which are currently applied for measuring the profile change of tubes gives us basic information such as axial locations and average magnitudes of deformations. However, the three-dimensional quantitative evaluation on circumferential locations, distributional angle, and size of deformations will have to be conducted to understand the effects of residual stresses increased by local deformations on corrosive cracking of tubes. Steam generator tubes of Korean standard nuclear power plants expanded within their tube-sheets by the explosive expansion method and suffered from corrosive cracks in the early stage of power operation. Thus, local deformations of steam generator tubes at the top of tube-sheet were measured with an advanced rotating probe and a laser profiling system for the two cases where the tubes expanded by the explosive expansion method and hydraulic expansion. Also, the trends of eccentricity, deflection, and over-expansion of tubes were evaluated. The advanced eddy current profilometry was confirmed to provide accurate information of local deformations compared with laser profilometry.

• 한국항해항만학회지
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• 제36권1호
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• pp.27-34
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• 2012

레저용 플로팅 건축물은 구조물 안전성, 건축물 용도, 건설 및 관리 경제성, 주변 지역이나 도시와 개발 연계성, 해양환경에의 영향 등을 고려할 때 입지선정에 대한 체계적 지침과 합리적 기준이 반드시 필요하다. 그러나 현재 우리나라에는 레저용 플로팅 건축물이 많이 계획되고 설치되는 시점에 있음에도 불구하고 입지선정에 관한 연구나 지침이 전혀 없는 실정이다. 따라서 본 연구는 레저용 플로팅 건축물의 입지선정을 위해 체계적 입지선정프로세스. 합리적 입지선정기준 및 입지평가지침을 제시하는 것이 목적이다. 본 연구에서는 지자체나 민간 기업에서 레저용 플로팅 건축물을 계획할 경우 체계적이고 합리적 입지선정에 활용할 수 있도록 입지선정과정, 입지선정기준, 입지평가항목 및 요인을 그림과 표로 알기 쉽게 제시하였다.

• 한국산학기술학회논문지
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• 제19권4호
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• pp.41-46
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• 2018

최근 러시아를 포함한 동북아 경제의 중요성이 커지고 있으며, 유라시아 이니셔티브 정책에 따르면 동북 아시아의 운송, 물류 및 연결성 향상은 미래 성장 동력의 과제 중 하나로 부상하고 있다. 그러나 각국의 차량 시스템이 다르기 때문에 국가 간 철도 차량은 원활하게 운행되지 못하고 있는 실정이다. 서로 다른 시스템의 차량을 안전하게 연계 운행하려는 시도는 유럽-러시아간에 활발하게 이루어지고 있는 실정이나, 동북아-러시아간에는 근래에 들어 연구가 시작되고 있는 추세이다. 특히, 화차의 연결기는 국내 및 중국은 미국의 AAR(Association of American Railroads) 규격을 기본으로 한 연결기를, 러시아는 국가 표준인 GOST(USSR State Standards)를 적용한 연결기를 사용하고 있어, 헤드 형상이 서로 상이하여 상호간 연결이 불가능한 실정일 뿐 아니라, 요구하고 있는 재료의 화학적 성질과 기계적 성질이 상이하다. 이에, 본 논문에서는 국내 철도용품 기술기준과 러시아의 GOST 규정을 만족하는 연결기를 상호 연결할 수 있는 가변형 연결기 및 연결기 어댑터를 개발하는데 있어, 각 국가에서 제시하고 있는 요구사항을 조사하고, 특히, 연결기에 대하여 요구하는 기계적 성질을 만족하는 재질을 개발하는 과정에서 시험을 통한 그 가능성을 분석하여, 향후 각 국가에서 안전하게 사용할 수 있는 연결기 어댑터 제작의 발판을 마련하고자 한다.

• 대한조선학회논문집
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• 제54권1호
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• pp.43-48
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• 2017

In recent years, the demand for ships and offshore platforms that can navigate and operate through the Arctic Ocean has been rapidly increasing due to global warming and large reservoirs of oil and natural gas in the area. Winterization design is one of the key issues to consider in the robust structural safety design and building of ships that operate in the Arctic and Sub-Arctic regions. However, international regulations for winterization design in Arctic condition regulated that only those ships and offshore platforms with a Polar Class designation and/or an alternative standard. In order to cope with the rising demand for operating in the Arctic region, existing and new Arctic vessels with a Polar Class designation are lacking to cover for adequate winterization design with HSE philosophy. Existing ships and offshore platform was not designed based on reliable data based on numerical and experiment studies. There are only designed as a performance and functional purposes. It is very important to obtain of reliable data and provide of design guidance of the anti-icing structures by taking the effects of low temperature into consideration. Therefore, the main objective of this paper reconsiders anti-icing design of aluminum helideck using the heating cable. To evaluate of reliable data and recommend of anti-icing design method, various types of analysis and methods can be applied in general. In the present study, finite element method carried out the thermal analysis with cold chamber testing for performance and capacity of heating cables.

• Corrosion Science and Technology
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• 제14권1호
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• pp.1-11
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• 2015

Local wall thinning and integrity degradation caused by several mechanisms, such as flow accelerated corrosion (FAC), cavitation, flashing and/or liquid drop impingements, are a main concern in carbon steel piping systems of nuclear power plant in terms of safety and operability. Thinned pipe management program (TPMP) had been developed and optimized to reduce the possibility of unplanned shutdown and/or power reduction due to pipe failure caused by wall thinning in the secondary side piping system. This program also consists of several technical elements such as prediction of wear rate for each component, prioritization of components for inspection, thickness measurement, calculation of actual wear and wear rate for each component. Decision making is associated with replacement or continuous service for thinned pipe components. Establishment of long-term strategy based on diagnosis of plant condition regarding overall wall thinning is also essential part of the program. Prediction models of wall thinning caused by FAC had been established for 24 operating nuclear plants. Long term strategies to manage the thinned pipe component were prepared and applied to each unit, which was reflecting plant specific design, operation, and inspection history, so that the structural integrity of piping system can be maintained. An alternative integrity assessment criterion and a computer program for thinned piping items were developed for the first time in the world, which was directly applicable to the secondary piping system of nuclear power plant. The thinned pipe management program is applied to all domestic nuclear power plants as a standard procedure form so that it contributes to preventing an accident caused by FAC.

• 한국건축시공학회지
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• 제6권1호
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• pp.87-91
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• 2006

Since water leakage and cracks are not the source of serious problems such as long-term lowering of performance and durability of a stricture, including damages to operating facilities of a structure, damages to internal finishing materials, exhibition, and goods, and pollution of residential environment, they might have led to development of positive coping skills; however, an instant loss of lives or property due to earthquake, explosion, typhoon, or a fire was indeed neglected. In these days, repair materials for leakage cannot help but being taken in temporary way without any noticeable countermeasure. This kind of repair is socially criticized many times that is defective construction even if this costs a lot. It was not arrange the standard for construction methods of sealer of injection type for leakage maintenance, even it has been used various type of construction methods for leakage part. In conclusion, we suggest that the construction methods of sealer of injection type for leakage maintenance for leakage to establish the leakage repairing technology as increase of structure demand. Therefore, it would be possible to provide a stage-by-stage solution by developing systematic research activities among the industry, schools, and research institutes to spread maintenance management techniques globally through technical solution to water leakage and cracks, acquisition of structural safety with prolonged durability for life cycle, reduction of water leakage repair expense s, and so on.

• 한국지진공학회논문집
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• 제24권3호
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• pp.123-128
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• 2020

Analysis of the 2016 Gyeongju earthquake and the 2017 Pohang earthquake showed the characteristics of a typical high-frequency earthquake with many high-frequency components, short time strong motion duration, and large peak ground acceleration relative to the magnitude of the earthquake. Domestic nuclear power plants were designed and evaluated based on NRC's Regulatory Guide 1.60 design response spectrum, which had a great deal of energy in the low-frequency range. Therefore, nuclear power plants should carry out seismic verification and seismic performance evaluation of systems, structures, and components by reflecting the domestic characteristics of earthquakes. In this study, high-frequency amplification factors that can be used for seismic verification and seismic performance evaluation of nuclear power plant systems, structures, and equipment were analyzed. In order to analyze the high-frequency amplification factor, five sets of seismic time history were generated, which were matched with the uniform hazard response spectrum to reflect the characteristics of domestic earthquake motion. The nuclear power plant was subjected to seismic analysis for the construction of the Korean standard nuclear power plant, OPR1000, which is a reactor building, an auxiliary building assembly, a component cooling water heat exchanger building, and an essential service water building. Based on the results of the seismic analysis, a high-frequency amplification factor was derived upon the calculation of the floor response spectrum of the important locations of nuclear power plants. The high-frequency amplification factor can be effectively used for the seismic verification and seismic performance evaluation of electric equipment which are sensitive to high-frequency earthquakes.

• 비파괴검사학회지
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• 제33권2호
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• pp.147-153
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• 2013

최근 가압경수로형 원전의 가압기 노즐과 안전단 사이의 이종용접부에서 일차수응력부식균열에 대한 건전성 확보가 중요한 관심사항으로 대두되고 있다. 가압기 노즐은 SA508 Gr.3 저합금강이며 안전단은 F316L 스테인리스강으로, 이들 두 재료 사이에 용접재로는 Alloy 82/182가 사용되었다. 재료 결함에 대한 건전성 평가를 위해서는 재료의 기계적 물성치, 특히 인장물성과 파괴물성이 확보되어야 한다. 그러나, 일반적인 재료 규격과 시험성적서에서는 상온의 인장물성이 제공되지만 고온의 인장물성과 파괴인성이 제공되지 않는다. 따라서, 본 논문에서는 상온과 원전 운전온도에서 SA508 Gr.3과 F316L 스테인리스강에 대한 인장시험과 J-R 파괴인성시험을 수행하고 그 결과를 수록하였다.

• 한국화재소방학회논문지
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• 제30권1호
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• pp.17-23
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• 2016

막구조물은 코팅된 직물을 주재료로 하는 구조로 연성을 가진 막을 사용하여 외부하중에 대해 안정된 형태를 유지하는 구조물을 말한다. 막에 의한 구조시스템은 대공간 시공이 가능하고 가벼우며 빛을 투과할 수 있는 등 자원 및 관리비용 절감 면에서 많은 이점을 가지고 있어 다양한 용도의 구조물에 적용되며 그 사용용도가 점차 확대되고 있는 실정이다. 하지만 막구조 건축물 및 막재가 다양해짐에도 불구하고 화재안전을 고려한 막재의 성능에 대한 기준은 미비한 실정이며 다양한 용도에 적합한 난연성능이 우수한 막재의 개발이 요구되고 있다. 따라서 본 연구에서는 시판되는 건축용 막재인 PTFE, PVDF와 PVF, ETFE 필름 막재의 방염 및 난연성능 시험 등을 통해 건축용 막재의 난연특성을 확인하였다.